The inherent law between fatigue behaviours of shear-type representative volume element and mode-II fatigue crack growth is found in the range of cycle plastic zone near the crack tip. Prediction models for mode-II fa...
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High energy density and intrinsic safety are the central pursuits in developing rechargeable Zinc-ion batteries (ZIBs). The capacity and stability of nickel cobalt oxide (NCO) cathode are unsatisfactory because of its...
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High energy density and intrinsic safety are the central pursuits in developing rechargeable Zinc-ion batteries (ZIBs). The capacity and stability of nickel cobalt oxide (NCO) cathode are unsatisfactory because of its semiconductor character. Herein, we propose a built-in electric field (BEF) approach by synergizing cationic vacancies and ferroelectric spontaneous polarization on cathode side to facilitate electron adsorption and suppress zinc dendrite growth on the anode side. Concretely, NCO with cationic vacancies was constructed to expand lattice spacing for enhanced zinc-ion storage. Heterojunction with BEF leads to the Heterojunction//Zn cell exhibiting a capacity of 170.3 mAh g−1 at 400 mA g−1 and delivering a competitive capacity retention of 83.3 % over 3000 cycles at 2 A g−1. We conclude the role of spontaneous polarization in suppressing zinc dendrite growth dynamics, which is conducive to developing high-capacity and high-safety batteries via tailoring defective materials with ferroelectric polarization on the cathode.
Floating nuclear power plant (FNPP) is built on the offshore platform and it is defined as a kind of Small and Modular reactor(SMR) due to its power level. The FNPP can provide power supply, fresh water and high tempe...
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U 3 Si 2 -FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physi...
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U 3 Si 2 -FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physic fuel performance code called BEEs for LWR fuels has been developed based on Multiphysics Object-Oriented Simulation Environment (MOOSE) using the Object-Oriented Programming (OOP) method. As a first step to verify the capability of BEEs, one problem has been conducted using BEEs and compared with the results from BISON and ABAQUS. Then, the most recently available U 3 Si 2 -FeCrAl behavior models have been coded in BEEs. Fuel performance analysis was conducted for U 3 Si 2 -FeCrAl fuel system using BEEs and comparisons with UO 2 -Zr4 and U 3 Si 2 -Zr4 were made in this work. The results show that U 3 Si 2 -FeCrAl fuel system can lower the fuel peaking temperature about 300 K and have flat radial temperature distribution which can mitigate or eliminate the fuel cracking during power up. Further, the pellet-cladding mechanic interaction can be delayed or fully eliminated employing U 3 Si 2 -FeCrAl fuel system in light water reactors (LWRs).
The elasto-plastic analysis for reactor Pressure Vessel seal is necessary because of nuclear safety is actively demanded. The existed work based on simplified way to simulate the seal ring, such as uniform stress, spr...
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During the course of a hypothetical severe accident in a light water reactor, spray systems could be used in the containment in order to prevent overpressure in case of a steam line break and to enhance the gas mixing...
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ISBN:
(纸本)9784890471676
During the course of a hypothetical severe accident in a light water reactor, spray systems could be used in the containment in order to prevent overpressure in case of a steam line break and to enhance the gas mixing in case of the presence of hydrogen. Thus these two effects induced by spray might compete with each other having an influence on the hydrogen risk. Focusing on the dynamic effect of spray, the impact of spray on the breakup of a light gas layer in a closed vessel is simulated and the experimental test evaluated here is TOSQAN 113 test that belongs to the dynamic part of SARNET FP6 benchmarks. ANSYS FLUENT 14.5 is chosen for the simulation tool and spray droplets are tracked with using the Euler-Lagrange approach-Discrete Phase Model (DPM). The code validation and several sensitivity studies are done to sum up the basic method of numerical simulation of spray with CFD code and assess the influence of calculation settings and parameters, such as turbulence model and spray boundary condition. The code validation shows that the results of calculations acceptably agree with the experimental data and the sensitivity studies reveal that spray boundary condition is a rather important factor for the accuracy of simulation. Conclusion gained in from the present work can provide some reference of the numerical analysis of containment.
Three primary design principles, meanwhile the design features, are carried through the R&D process of Chinese Small Module reactor (ACP100): integral layout, compact design and modularized configuration. As a sub...
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ISBN:
(纸本)9784890471676
Three primary design principles, meanwhile the design features, are carried through the R&D process of Chinese Small Module reactor (ACP100): integral layout, compact design and modularized configuration. As a substantial demonstration of the above design conceptions, an upper plenum built-in pressurizer is proposed for the pressure control systemdesign for Chinese SMR. In this design, branches with large diameters connected to the primary loop (i.e. surge line, etc.) are eliminated, and this will significantly reduce the LOCA possibility due to the pressure boundary breach. This study mainly focuses on the feature of responses of the built-in pressure control system during the system transients, such as step load increase/decrease, ramp load increase/decrease and partial loss of electrical load. Initial status of the plant, assumptions, postulated transient condition and methodology of this analysis are described in the first section. Important thermal hydraulic parameters that can picture the transient characteristics of the coolant system are given in the second section. It shows that, during those transients, no reactor safety related signals or safety guard features are triggered or actived. It also shows that Nuclear/thermal power response rapidly and stably, and average coolant temperature and system pressure are welled controlled within the range of normal deviation of the set point values of safety related system. This study results get a good agreement with the operating experiment study of the build-in pressure control system.
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